Physics:COMPASS tokamak
COMPASS tokamak vacuum chamber | |
Device Type | Tokamak |
---|---|
Location | Prague, Czech Republic |
Affiliation | Czech Academy of Sciences |
Technical specifications | |
Major Radius | 0.56 m (1 ft 10 in) |
Minor Radius | 0.23 m (9.1 in) |
Magnetic field | 0.9–2.1 T (9,000–21,000 G) |
Heating power | 2 × 0.3 MW |
Discharge duration | 0.5 s (pulsed) |
Plasma current | 360 kA |
History | |
Year(s) of operation | 1992–2002 (in United Kingdom ) 2006 – 2021 (in CZ) |
Links | |
Website | COMPASS Tokamak |
Other links |
COMPASS, short for Compact Assembly, is a compact tokamak fusion energy device originally completed at the Culham Science Centre in 1989, upgraded in 1992, and operated until 2002. It was designed as a flexible research facility dedicated mostly to plasma physics studies in circular and D-shaped plasmas.
When it was decommissioned at Culham, it was offered to the European Commission and found a new home at the Institute of Plasma Physics of the Czech Academy of Sciences in Prague where it began operations once again in 2006.[1][2][3][4] It officially ended its experimental runs on 20 August 2021 and will be disassembled to leave room for a new device, COMPASS-U.[5]
History
The first plasma in COMPASS was produced in 1989 in a C-shaped vacuum vessel, i.e., in a simpler vessel with a circular cross-section. Pioneering experiments followed, including for example the ITER-relevant tests of magnetic field correction with saddle coils for Resonant magnetic perturbations (RMP) experiments or experiments with non-inductive current drive in plasma.
The operation of tokamak was restarted with a D-shaped vacuum vessel in 1992. The operation mode with high plasma confinement (H-mode) was achieved, which represents a reference operation ("standard scenario") for the ITER tokamak. The COMPASS tokamak is one of the smallest tokamaks able to operate in H-mode, with a major radius 0.6 m and height of approximately 0.7 m. Due to its size and shape, the COMPASS plasmas correspond to one tenth (in the linear scale) of the ITER plasmas. Besides COMPASS, there are only two operational tokamaks in Europe with ITER-like configuration capable of H-mode, the Joint European Torus (JET) at Culham and the ASDEX Upgrade at the Institut für Plasmaphysik in Garching, Germany.
In 2002, British scientists started alternative research on larger, spherical tokamak MAST. Operation of COMPASS was discontinued due to insufficient resources for the operation of both tokamaks, however, the planned research program was not complete. The European Commission and UKAEA sent COMPASS to the Institute of Plasma Physics in Prague in the autumn of 2004. The machine restarted operations in 2006 and operated continually until its last "shot" on 20 August 2021. During its operational time in Prague, COMPASS carried out 21,000 experimental shots.
(As of August 2021), plans are to dispose of COMPASS to make way for a significantly larger machine, COMPASS-U (for Upgrade).
COMPASS and COMPASS-U
Parameters | Values[6] | Values after planned upgrade in 2021[7] |
---|---|---|
Major radius R | 0.56 m | 0.84 m |
Minor radius a | 0.23 m | 0.28 m |
Plasma current Ip (max) | 360 kA | 2 MA |
Magnetic field BT | 0.9 T - 2.1 T | 5 T |
Vacuum pressure | 1×10−6 Pa | |
Elongation | 1.8 | |
Plasma shape | D, SND, elliptical, circular | |
Pulse length(max) | ~ 0.5 s | 5 s |
Beam heating PNBI 40 keV | 2 × 0.3 MW | 4-5 MW |
See also
- List of fusion experiments
- ELM (Edge Localized Mode)
- Ball-pen probe
- Langmuir probe
- Thomson scattering
- Resonant magnetic perturbations
References
- ↑ Pánek, R.; O. Bilyková; V. Fuchs; M. Hron; P. Chráska; P. Pavlo; J. Stöckel; J. Urban et al. (2006). "Reinstallation of the COMPASS-D tokamak in IPP ASCR". Czechoslovak Journal of Physics 56 (2): 125–137. doi:10.1007/s10582-006-0188-1. ISSN 1572-9486. Bibcode: 2006CzJPh..56B.125P.
- ↑ Weinzettl, V.; R. Panek; M. Hron; J. Stockel; F. Zacek; J.Havlicek; P.Bilkova; D.I.Naydenkova et al. (2011). "Overview of the COMPASS diagnostics". Fusion Engineering and Design 86 (6–8): 1224–1231. doi:10.1016/j.fusengdes.2010.12.024.
- ↑ Panek, R.; J. Adamek; M. Aftanas; P. Bilkova; P. Böhm; F. Brochard; P. Cahyna; J. Cavalier et al. (2015). "Status of the COMPASS tokamak and characterization of the first H-mode". Plasma Phys. Control. Fusion 58 (1): 014015. doi:10.1088/0741-3335/58/1/014015. Bibcode: 2016PPCF...58a4015P.
- ↑ "Tokamak". http://www.ipp.cas.cz/vedecka_struktura_ufp/tokamak/.
- ↑ "Curtain Call for the COMPASS Tokamak". 13 September 2021. https://www.iter.org/newsline/-/3661.
- ↑ COMPASS on the Institute of Plasma Physics of CAS, http://www.ipp.cas.cz/vedecka_struktura_ufp/tokamak/tokamak_compass/, retrieved 2018-05-28
- ↑ "COMPASS Upgrade on the Institute of Plasma Physics of CAS". http://www.ipp.cas.cz/vedecka_struktura_ufp/tokamak/compass_u/.
External links
https://iopscience.iop.org/article/10.1088/0741-3335/58/1/014015
Original source: https://en.wikipedia.org/wiki/COMPASS tokamak.
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